• Nuclear Engineering and Technology
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• 제53권3호
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• pp.949-959
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• 2021

The current study aims to explore the shielding properties of multi-component borate-based glass series. Seven glass-samples with composition of (80-y)H₃BO₃-10ZnO-10Na₂O-yBaO where (y = 0, 5, 10, 15, 20, 25 and 30 mol.%) were synthesized by melt-quench method. Various shielding features for photons, neutrons, and protons were determined for all prepared samples. XCOM, Phy-X program, and SRIM code were performed to determine and explain several shielding properties such as equivalent atomic number, exposure build-up factor, specific gamma-ray constants, effective removal cross-section (Σ_R), neutron scattering and absorption, Mass Stopping Power (MSP) and projected range. The energy ranges for photons and protons were 0.015-15 MeV and 0.01-10 MeV, respectively. The mass attenuation coefficient (μ/ρ) was also determined experimentally by utilizing two radioactive sources (¹⁶⁶Ho and ¹³⁷Cs). Consistent results were obtained between experimental and XCOM values in determining μ/ρ of the new glasses. The addition of BaO to the glass matrix led to enhance the μ/ρ and specific gamma-ray constants of glasses. Whereas the remarkable reductions in Σ_R, MSP, and projected range values were reported with increasing BaO concentrations. The acquired results nominate the use of these glasses in different radiation shielding purposes.

• 한국안전학회지
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• 제33권6호
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• pp.144-156
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• 2018

Level 3 Probabilistic Safety Assessment (PSA) is performed for the risk assessment that calculates radioactive material dispersion to the environment. This risk assessment is performed with a tool of MELCOR Accident Consequence Code System (MACCS2 or WinMACCS). For the off-site consequence analysis of multi-unit nuclear power plant (NPP) accident, the single location (Center Of Mass, COM) method has been usually adopted with the assumption that all the NPPs in the nuclear site are located at the same COM point. It was well known that this COM calculation can lead to underestimated or overestimated radionuclide concentration. In order to overcome this underestimation or overestimation of radionuclide concentrations in the COM method, Multiple Location (ML) method was developed in this study. The radionuclide concentrations for the individual NPPs are separately calculated, and they are summed at every location in the nuclear site by the post-processing of radionuclide concentrations that is based on two-dimensional Gaussian Plume equations. In order to demonstrate the efficiency of the ML method, radionuclide concentrations were calculated for the six-unit NPP site, radionuclide concentrations of the ML method were compared with those by COM method. This comparison was performed for conditions of constant weather, yearly weather in Korea, and four seasons, and the results were discussed. This new ML method (1) improves accuracy of radionuclide concentrations when multi-unit NPP accident occurs, (2) calculates realistic atmospheric dispersion of radionuclides under various weather conditions, and finally (3) supports off-site emergency plan optimization. It is recommended that this new method be applied to the risk assessment of multi-unit NPP accident. This new method drastically improves the accuracy of radionuclide concentrations at the locations adjacent to or very close to NPPs. This ML method has a great strength over the COM method when people live near nuclear site, since it provides accurate radionuclide concentrations or radiation doses.

• 대한방사선기술학회지:방사선기술과학
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• 제31권1호
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• pp.89-95
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• 2008

국제원자력기구의 TRS-398 측정 프로토콜을 임상에 적용하기 위해서는 사용하는 빔과 전리함에 대한 선질 보정인자가 필요하다. 본 연구에서는 몬테칼로 계산코드(DOSRZnrc/EGSnrc)를 사용하여 상용의 평판형전리함에 대한 고에너지 전자선($4{\sim}20\;MeV$)에서의 선질보정인자를 계산하였다. 계산결과를 프로토콜에서 제시하는 값과 비교한 결과 $5{\sim}20\;MeV$에서 약 1% 이내로 일치하였으며 4 MeV의 경우에는 약 1.9% 차이를 보였다. 본 연구 방법은 선질보정인자를 독립적으로 결정하는 방법의 하나로서 프로토콜에서 주어진 값들의 확인이 필요하거나 또는 새로운 모델의 전리함을 사용하는 경우에 응용될 수 있다.

• Journal of Mechanical Science and Technology
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• 제17권9호
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• pp.1380-1387
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• 2003

When a cold HPSI (High pressure Safety Injection) fluid associated with an overcooling transient, such as SGTR (Steam Generator Tube Rupture), MSLB (Main Steam Line Break) etc., enters the cold legs of a stagnated primary coolant loop, thermal stratification phenomena will arise due to incomplete mixing. If the stratified flow enters the downcomer of the reactor pressure vessel, severe thermal stresses are created in a radiation embrittled vessel wall by local overcooling. As general thermal-hydraulic system analysis codes cannot properly predict the thermal stratification phenomena, RG 1.154 requires that a detailed thermal-mixing analysis of PTS (pressurized Thermal Shock) evaluation be performed. Also. previous PTS studies have assumed that the thermal stratification phenomena generated in the stagnated loop side of a partially stagnated primary coolant loop are neutralized in the vessel downcomer by the strong flow from the unstagnated loop. On the basis of these reasons, this paper focuses on the development of a 3-dimensional thermal-mixing analysis model using PHOENICS code which can be applied to both partial and total loop stagnated cases. In addition, this paper verifies the fact that, for partial loop stagnated cases, the cold plume generated in the vessel downcomer due to the thermal stratification phenomena of the stagnated loop is almost neutralized by the strong flow of the unstagnated loop but is not fully eliminated.

• Structural Engineering and Mechanics
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• 제21권4호
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• pp.437-450
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• 2005

In this study, a complete analysis of soil-structure interaction problems is presented which includes a modelling of the near surrounding of the building (near-field) and a special description of the wave propagation process in larger distances (far-field). In order to reduce the computational effort which can be very high for time domain analysis of wave propagation problems, a special approach based on similarity transformation of the infinite domain on the near-field/far-field interface is applied for the wave radiation of the far-field. The near-field is discretised with standard Finite Elements, which also allows to introduce non-linear material behaviour. In this paper, a new approach to calculate the involved convolution integrals is presented. This approximation in time leads to a dramatically reduced computational effort for long simulation times, while the accuracy of the method is not affected. Finally, some benchmark examples are presented, which are compared to a coupled Finite Element/Boundary Element approach. The results are in excellent agreement with those of the coupled Finite Element/Boundary Element procedure, while the accuracy is not reduced. Furthermore, the presented approach is easy to incorporate in any Finite Element code, so the practical relevance is high.

• 방사성폐기물학회지
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• 제18권4호
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• pp.537-548
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• 2020

Currently, radioactive waste for disposal has been restricted to low and intermediate level radioactive waste generated during operation of nuclear power plants, and these radioactive wastes were managed and disposed of the 200 L and 320 L of steel drums. However, it is expected that it will be difficult to manage a large amount of decommissioning waste of the Kori unit 1 with the existing drums and transportation containers. Accordingly, the KORAD is currently developing various and large-sized containers for packaging, transportation, and disposal of decommissioning waste. In this study, the radiation exposure doses of workers and the public were evaluated using RADTRAN computational analysis code in case of the domestic on-road transportation of new package and transportation containers under development. The results were compared with the domestic annual dose limit. In addition, the sensitivity of the expected exposure dose according to the change in the leakage rate of radionuclides in the waste packaging was evaluated. As a result of the evaluation, it was confirmed that the exposure dose under normal and accident condition was less than the domestic annual exposure dose limit. However, in the case of a number of loading and unloading operations, working systems should be prepared to reduce the exposure of workers.

• Nuclear Engineering and Technology
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• 제56권7호
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• pp.2748-2755
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• 2024

This paper presents two new methods for variance reduction for shielding calculation in Monte Carlo radiation transport. One method is CADIS-NEE, which combines Consistent Adjoint Driven Importance Sampling (CADIS) and next-event estimator (NEE) methods to increase the calculation efficiency of tallies at points. The other is CADIS-deterministic transport (DXTRAN), which combines CADIS and DXTRAN to obtain higher performance than using CADIS and DXTRAN separately. The combination processes are derived and implemented in the hybrid Monte-Carlo-Deterministic particle-transport code NECP-MCX. Various problems are tested to demonstrate the effectiveness of the two methods. According to the results, the two combination methods have higher efficiency than using CADIS, NEE or DXTRAN separately. In a long-distance photon-transport problem, CADIS-NEE converges faster than NEE and the figure of merit (FOM) of CADIS-NEE is 75.6 times of NEE. In a labyrinthine problem, CADIS-DXTRAN's FOM surpasses that of DXTRAN and CADIS by a factor of 45.3 and 17.7, respectively. Therefore, it is advisable to employ these two novel methods selectively in appropriate scenarios to reduce variance.

• 한국식품영양과학회지
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• 제34권5호
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• pp.605-612
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• 2005

방사선 생체손상의 방어 및 회복에 높은 효과를 나타내는 생약조합을 도출하고자 하였다. 이전의 연구에서 6가지 기존 보기${\cdot}$보혈 한약처방제의 방어효과를 검색하여, 재생조직 방어에는 사물탕 및 보중익기탕이, 조혈계 방어에는 보중익기탕 및 사물탕이 높은 효과를 나타내는 것으로 보고된바 있다. 본 연구에서 기존 6가지 처방제의 면역 세포 활성화 효과를 검색한 결과 모두 높은 효과를 나타내지 않았다. 따라서, 처방제의 구성 생약 각각의 효과검증 결과를 바탕으로 재생조직 방어, 조혈계 방어, 면역조혈계 회복 증진 효과를 동시에 높게 나타내는 새로운 생약조합을 도출하였다. 즉, 당귀, 천궁, 백작약을 동일 무게 비율로 혼합하여 열수 추출한 것을 새로운 생약복합물 HIM-I으로 개발하였으며 그 효과를 검정하였다. 본 생약복합물 HIM-I은 면역 세포 활성화에서는 상기한 한약처방제보다 월등하게 높은 효과를 보였으며, 조혈계 촉진효과도 높은 것으로 나타났다. 또한, 재생조직 및 면역조혈계의 방어 측면에서도 사물탕 및 보중익기탕과 같은 높은 효과를 보였다. 한편, 시험관 내에서 높은 항산화 효과를 나타내는 것으로 보아, 이 항산화 작용이 방사선 손상에 대한 방어효과의 작용기전 중의 하나로 생각되었다. 이상의 결과로 보아, 생약복합물 HIM-I은 재생조직방어, 조혈계 방어, 면역조혈계 회복 증진 효과를 동시에 나타냄으로써 방사선뿐만 아니라 여러 가지 원인으로부터 생체를 방호하고 회복시키는데 유용할 것으로 생각된다.

• Nuclear Engineering and Technology
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• 제48권5호
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• pp.1273-1279
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• 2016

Production of iodine-131 by neutron activation of tellurium in tellurium dioxide ($TeO_2$) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gaswelding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ${\leq}10^{-4}mbr.L/s$, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics). To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to $600^{\circ}C$ with the appearance of deformations on lids beyond $450^{\circ}C$. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes-convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from4 hours of irradiation at a power level of 0.5MWup to 35 hours (7 h/d for 5 days a week) at 1.5MW. The results showthat the irradiated targets are tight because no iodine-131 was released in the atmosphere of the reactor building and in the reactor cooling water of the primary circuit.

• 한국방사선학회논문지
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• 제6권2호
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• pp.143-149
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• 2012

오늘날 의료영상매체의 획기적인 발전으로 각 병원에서 최신 의료장비를 도입함으로써 첨단화, 디지털화로 급변하는 추세이다. 이러한 움직임에 발맞추어 방사선 종양학과에서도 CR system을 도입하여 film system의 단점을 보완하고 병원에서 사용하고 있는 Picture Archiving and Communication System(PACS)과 Electronic Medical Record (EMR) , 그리고 Radiation therapy Treatment Planning system(RTP)의 network를 원활히 하여 업무효율 증대 및 환자에 대한 의료의 질 개선과 서비스 향상을 이루고자 하고 있는데, 방사선 종양학과의 Computed Radiography system(CR system)을 이용하여 PACS에 통합한 사례를 소개하고 그 유용성을 평가하고자 한다. 의료용 선형가속기인 MEVATRON-MX를 이용하여 현재 시행하고 있는 정도관리 중 Gantry, Collimator Star Shot, Light vs. Radiation Field Accuracy, HDR QA(Dwell position accuracy)를 시행하여 PACS 상에 구현하였고 모니터 상에서 디지털 영상을 통한 QA가 가능한지 확인하였다. 또한, 현재 S병원에서 사용 중인 Operation Control System(OCS)과 연동하여 치료에 필요한 코드를 각각의 치료에 부과하여 네트워크로 연결, CR상에 입력한 order가 나타나도록 하였으며, Planning System인 Pinacle과 PACS상의 지원 data 오류를 해결하여 PACS 상에서도 Planning 영상을 볼 수 있도록 하였다. CR system을 이용하여 L-gram, simulation image, planning image를 병원 내 어느 곳에서나 영상을 조회하고 볼 수 있게 PACS에 통합 구축되어있다. Filmless 환경에서 Dosimetry용 IP를 이용하여 Light/Radition field size 일치, gantry rotation axis의 정확성, collimator rotation axis의 정확성, brachy therapy의 Dwell position check등 QA의 시행이 가능하였다. CR system을 이용하여 방사선 종양학과에서 얻어지는 영상을 PACS에 통합함으로써 작업시간 단축과 그에 따른 불필요한 인력소모의 감소 등으로 인하여 업무효율이 증대되었지만 향후 환자정보에 대한 보안을 필요로 한다.